Main steam pressure control method and device of multi-module nuclear thermoelectric system

Abstract

The invention relates to a main steam pressure control method and device for a multi-module nuclear thermoelectric system, and the method comprises the steps: obtaining a main steam pressure measurement value of the multi-module nuclear thermoelectric system under the condition that the opening degree of a main steam adjustment valve of the multi-module nuclear thermoelectric system is fixed; if the deviation between the main steam pressure measurement value and the main steam pressure set value of the multi-module nuclear thermoelectric system is greater than a first threshold value, determining the adjustment amount of a water feed pump rotating speed set value and the adjustment amount of a thermal power set value of the multi-module nuclear thermoelectric system according to the deviation; and adjusting the rotating speed set value of the water feeding pump of the multi-module nuclear thermoelectric system based on the adjustment amount of the rotating speed set value of the water feeding pump, and adjusting the thermal power set value of at least one nuclear steam supply system module of the multi-module nuclear thermoelectric system based on the adjustment amount of the thermal power set value so as to reduce the deviation.

Description

Technical Field

[0001] The present disclosure relates to the field of nuclear energy science and engineering, and in particular to a main steam pressure control method and device for a multi-module nuclear thermal power system. Background Art

[0002] A multi-module nuclear thermal power system refers to a system where multiple nuclear steam supply system modules use nuclear energy to heat water to form hot steam, which is then gathered as main steam and then diverted to the steam turbine and the heating system. The steam turbine can generate electricity based on the steam obtained, and the heating system can provide thermal energy or mechanical energy to the outside based on the steam obtained. Generally speaking, a main steam regulating valve is set in front of the steam turbine to adjust the distribution ratio of the main steam between the steam turbine and the heating system to achieve the effect of "the heating system load is met first, and the remaining steam is used for power generation".

[0003] However, in the related art, when the opening of the main steam regulating valve in front of the steam turbine of the multi-module nuclear thermal power system is fixed, it is impossible to effectively adjust the steam pressure entering the heating system, so that the heat load of the heating system cannot be accurately met, resulting in unstable energy supply effect of the heating system. Summary of the invention

[0004] In order to overcome the problems existing in the related art, the embodiments of the present disclosure provide a main steam pressure control method and device for a multi-module nuclear thermal power system to solve the defects in the related art.

[0005] According to a first aspect of an embodiment of the present disclosure, a main steam pressure control method for a multi-module nuclear thermal power system is provided, the method comprising:

[0006] When the opening of the main steam regulating valve of the multi-module nuclear thermal power system is fixed, obtaining a main steam pressure measurement value of the multi-module nuclear thermal power system;

[0007] If the deviation between the main steam pressure measurement value and the main steam pressure setting value of the multi-module nuclear thermal power system is greater than a first threshold value, determining an adjustment amount of a feedwater pump speed setting value and an adjustment amount of a thermal power setting value of the multi-module nuclear thermal power system according to the deviation;

[0008] The feedwater pump speed setting value of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the feedwater pump speed setting value, and the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setting value to reduce the deviation.

[0009] In one embodiment of the present disclosure, determining the adjustment amount of the feedwater pump speed setting value and the adjustment amount of the thermal power setting value of the multi-module nuclear thermal power system according to the deviation includes:

[0010] Determining an adjustment amount of a feedwater pump speed setting value of the multi-module nuclear thermal power system according to the deviation and a first proportional-integral control algorithm;

[0011] An adjustment amount of a thermal power set point of the multi-module nuclear thermal power system is determined based on the deviation and a second proportional-integral control algorithm.

[0012] In one embodiment of the present disclosure, the adjusting the feedwater pump speed setting value of the multi-module nuclear thermal power system based on the adjustment amount of the feedwater pump speed setting value includes:

[0013] Based on the adjustment amount of the feed water pump speed setting value, the hydraulic coupling scoop position setting value of the feed water pump of the multi-module nuclear thermal power system is adjusted to adjust the speed of the feed water pump.

[0014] In one embodiment of the present disclosure, the step of adjusting the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setting value comprises:

[0015] The thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setting value, so that the nuclear steam supply system module adjusts the feed water flow based on the adjusted thermal power setting value.

[0016] In one embodiment of the present disclosure, the step of adjusting the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setting value comprises:

[0017] The thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setting value, so that the nuclear steam supply system module adjusts the nuclear power based on the adjusted thermal power setting value.

[0018] In one embodiment of the present disclosure, the step of adjusting the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setting value comprises:

[0019] The thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setting value, so that the nuclear steam supply system module adjusts the primary loop coolant flow based on the adjusted thermal power setting value.

[0020] In one embodiment of the present disclosure, the method further includes:

[0021] According to the deviation, determining at least one nuclear steam supply system module participating in main steam pressure control among all the nuclear steam supply system modules of the multi-module nuclear thermal power system;

[0022] The step of adjusting the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setting value comprises:

[0023] Based on the adjustment amount of the thermal power setting value, the thermal power setting value of at least one nuclear steam supply system module participating in the main steam pressure control in the multi-module nuclear thermal power system is adjusted.

[0024] In one embodiment of the present disclosure, the method further includes:

[0025] Determining at least one nuclear steam supply system module participating in main steam pressure control among all the nuclear steam supply system modules of the multi-module nuclear thermal power system according to a user instruction;

[0026] The step of adjusting the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setting value comprises:

[0027] Based on the adjustment amount of the thermal power setting value, the thermal power setting value of at least one nuclear steam supply system module participating in the main steam pressure control in the multi-module nuclear thermal power system is adjusted.

[0028] In one embodiment of the present disclosure, the feedwater pump speed setting value of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the feedwater pump speed setting value, and the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setting value to reduce the deviation, including:

[0029] The feedwater pump speed setting value of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the feedwater pump speed setting value, and the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setting value, until the deviation is reduced below a second threshold, wherein the second threshold is smaller than the first threshold.

[0030] In one embodiment of the present disclosure, the main steam regulating valve of the multi-module nuclear thermal power system is used to fix the opening when the turbine air intake is fixed or the turbine is under maintenance.

[0031] According to a second aspect of an embodiment of the present disclosure, a main steam pressure control device for a multi-module nuclear thermal power system is provided, the device comprising:

[0032] An acquisition module, used for acquiring a main steam pressure measurement value of the multi-module nuclear thermal power system when the opening of the main steam regulating valve of the multi-module nuclear thermal power system is fixed;

[0033] a determination module, configured to determine an adjustment amount of a feedwater pump speed setting value and an adjustment amount of a thermal power setting value of the multi-module nuclear thermal power system according to the deviation between the main steam pressure measurement value and the main steam pressure setting value of the multi-module nuclear thermal power system if the deviation between the main steam pressure measurement value and the main steam pressure setting value of the multi-module nuclear thermal power system is greater than a first threshold value;

[0034] An adjustment module is used to adjust the feedwater pump speed of the multi-module nuclear thermal power system based on the adjustment amount of the feedwater pump speed setting value, and to adjust the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setting value, so as to reduce the deviation.

[0035] In one embodiment of the present disclosure, the determining module is used to:

[0036] Determining an adjustment amount of a feedwater pump speed setting value of the multi-module nuclear thermal power system according to the deviation and a first proportional-integral control algorithm;

[0037] An adjustment amount of a thermal power set point of the multi-module nuclear thermal power system is determined based on the deviation and a second proportional-integral control algorithm.

[0038] In one embodiment of the present disclosure, when the adjustment module is used to adjust the feedwater pump speed setting value of the multi-module nuclear thermal power system based on the adjustment amount of the feedwater pump speed setting value, it is used to:

[0039] Based on the adjustment amount of the feed water pump speed setting value, the hydraulic coupling scoop position setting value of the feed water pump of the multi-module nuclear thermal power system is adjusted to adjust the speed of the feed water pump.

[0040] In one embodiment of the present disclosure, when the adjustment module is used to adjust the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setting value, it is used to:

[0041] The thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setting value, so that the nuclear steam supply system module adjusts the feed water flow based on the adjusted thermal power setting value.

[0042] In one embodiment of the present disclosure, when the adjustment module is used to adjust the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setting value, it is used to:

[0043] The thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setting value, so that the nuclear steam supply system module adjusts the nuclear power based on the adjusted thermal power setting value.

[0044] In one embodiment of the present disclosure, when the adjustment module is used to adjust the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setting value, it is used to:

[0045] The thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setting value, so that the nuclear steam supply system module adjusts the primary loop coolant flow based on the adjusted thermal power setting value.

[0046] In one embodiment of the present disclosure, the device further includes a selection module, configured to:

[0047] According to the deviation, determining at least one nuclear steam supply system module participating in main steam pressure control among all the nuclear steam supply system modules of the multi-module nuclear thermal power system;

[0048] When the adjustment module is used to adjust the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setting value, it is used to:

[0049] Based on the adjustment amount of the thermal power setting value, the thermal power setting value of at least one nuclear steam supply system module participating in the main steam pressure control in the multi-module nuclear thermal power system is adjusted.

[0050] In one embodiment of the present disclosure, the device further includes a selection module, configured to:

[0051] Determining at least one nuclear steam supply system module participating in main steam pressure control among all the nuclear steam supply system modules of the multi-module nuclear thermal power system according to a user instruction;

[0052] When the adjustment module is used to adjust the thermal power set value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power set value, it is used to: adjust the thermal power set value of at least one nuclear steam supply system module participating in the main steam pressure control in the multi-module nuclear thermal power system based on the adjustment amount of the thermal power set value.

[0053] In one embodiment of the present disclosure, the adjustment module is used to:

[0054] The feedwater pump speed setting value of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the feedwater pump speed setting value, and the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setting value, until the deviation is reduced below a second threshold, wherein the second threshold is smaller than the first threshold.

[0055] In one embodiment of the present disclosure, the main steam regulating valve of the multi-module nuclear thermal power system is used to fix the opening when the turbine air intake is fixed or the turbine is under maintenance.

[0056] According to a third aspect of an embodiment of the present disclosure, there is provided a computer program product, comprising a computer program / instruction, which implements the steps of the method described in the first aspect when the computer program / instruction is executed by a processor.

[0057] According to a fourth aspect of an embodiment of the present disclosure, an electronic device is provided, comprising a memory and a processor, wherein the memory is used to store computer instructions executable on the processor, and the processor is used to implement the method described in the first aspect when executing the computer instructions.

[0058] According to a fifth aspect of an embodiment of the present disclosure, there is provided a computer-readable storage medium on which a computer program is stored, and when the program is executed by a processor, the method described in the first aspect is implemented.

[0059] The technical solution provided by the embodiments of the present disclosure may have the following beneficial effects:

[0060] The main steam pressure control method of the multi-module nuclear thermal power system provided in the embodiment of the present disclosure obtains the main steam pressure measurement value of the multi-module nuclear thermal power system to determine the deviation between the main steam pressure measurement value and the main steam pressure setting value when the deviation between the two is greater than a first threshold value, and adjusts the system's feedwater pump speed setting value and the thermal power setting value of at least one nuclear steam supply system module according to the deviation, thereby reducing the deviation. When the set value of the main steam pressure deviates from the measured value, the method reduces the above deviation by adjusting the system's feedwater pump speed and the thermal power of at least one nuclear steam supply system module, and can quickly respond to the heat load fluctuation of the heating system when the opening of the main steam regulating valve is fixed, so that the steam pressure entering the heating system meets the heat load demand of the heating system, and improves the stability of the heating effect of the heating system. BRIEF DESCRIPTION OF THE DRAWINGS

[0061] The accompanying drawings, which are incorporated in and constitute a part of this specification, illustrate embodiments consistent with the invention and, together with the description, serve to explain the principles of the invention.

[0062] Figure 1 is a schematic structural diagram of a multi-module nuclear thermal power system shown in an exemplary embodiment of the present disclosure;

[0063] Figure 2 is a flow chart of a main steam pressure control method of a multi-module nuclear thermal power system shown in an exemplary embodiment of the present disclosure;

[0064] Figure 3 is a main steam pressure control logic diagram of a multi-module nuclear thermal power system shown in an exemplary embodiment of the present disclosure;

[0065] Figure 4 is a structural schematic diagram of a main steam pressure control device of a multi-module nuclear thermal power system shown in an exemplary embodiment of the present disclosure;

[0066] Figure 5 It is a structural block diagram of an electronic device shown in an exemplary embodiment of the present disclosure. DETAILED DESCRIPTION

[0067] Exemplary embodiments will be described in detail herein, examples of which are shown in the accompanying drawings. When the following description refers to the drawings, the same numbers in different drawings represent the same or similar elements unless otherwise indicated. The embodiments described in the following exemplary embodiments do not represent all embodiments consistent with the present disclosure. Instead, they are merely examples of devices and methods consistent with some aspects of the present disclosure as detailed in the appended claims.

[0068] The terms used in this disclosure are for the purpose of describing specific embodiments only and are not intended to limit the disclosure. The singular forms of "a", "said" and "the" used in this disclosure and the appended claims are also intended to include plural forms unless the context clearly indicates otherwise. It should also be understood that the term "and / or" used herein refers to and includes any or all possible combinations of one or more associated listed items.

[0069] It should be understood that although the terms first, second, third, etc. may be used in the present disclosure to describe various information, such information should not be limited to these terms. These terms are only used to distinguish the same type of information from each other. For example, without departing from the scope of the present disclosure, the first information may also be referred to as the second information, and similarly, the second information may also be referred to as the first information. Depending on the context, the word "if" as used herein may be interpreted as "at the time of" or "when" or "in response to determining".

[0070] A multi-module nuclear thermal power system refers to a system where multiple nuclear steam supply system modules use nuclear energy to heat water to form hot steam, which is then gathered as main steam and then diverted to the steam turbine and the heating system. The steam turbine can generate electricity based on the steam obtained, and the heating system can provide thermal energy or mechanical energy to the outside based on the steam obtained. Generally speaking, a main steam regulating valve is set in front of the steam turbine to adjust the distribution ratio of the main steam between the steam turbine and the heating system to achieve the effect of "the heating system load is met first, and the remaining steam is used for power generation".

[0071] However, in the related art, when the opening of the main steam regulating valve in front of the steam turbine of the multi-module nuclear thermal power system is fixed, it is impossible to effectively adjust the steam pressure entering the heating system, so that the heat load of the heating system cannot be accurately met, resulting in unstable energy supply effect of the heating system.

[0072] Based on this, on the first aspect, at least one embodiment of the present disclosure provides a main steam pressure control method for a multi-module nuclear thermal power system. This method can ensure the stability of the heating effect of the heating system by dynamically adjusting the system's feedwater pump speed and the thermal power of at least one nuclear steam supply system module when the opening of the main steam regulating valve (i.e., the steam valve in front of the steam turbine used to control the steam flow entering the steam turbine) of the multi-module nuclear thermal power system is fixed.

[0073] The above multi-module nuclear thermal power system is equipped with multiple nuclear steam supply system modules, each of which can provide a high-temperature inert gas flow to heat the supercooled water through nuclear fission. The coupling effect between the multiple nuclear steam supply system modules is relatively large, and the core and the direct-flow evaporator in the nuclear steam supply system module are arranged side by side, which makes the coupling effect inside the nuclear steam supply system module relatively large. Therefore, the above multi-module nuclear thermal power system cannot use the main steam pressure control method of the main pipe of the thermal power station to control the main steam pressure.

[0074] First, attach Figure 1 Taking the multi-module nuclear thermal power system shown as an example, the structure of the multi-module nuclear thermal power system is explained.

[0075] The generator set includes 6 nuclear steam supply system modules, a condensate heating system (only the feed water pump included therein is shown in the figure), a condenser, a steam turbine (not shown in the figure), a generator (not shown in the figure), a heating system, etc. It should be understood that there is no limit to the number of nuclear steam supply system modules in the generator set, and the 6 nuclear steam supply system modules here are only examples.

[0076] The condensate heating system may include a condensate pump, a shaft seal heater, multiple low-pressure heaters, a deaerator, a feed water pump, and multiple high-pressure heaters connected in sequence by pipelines; the outlet of the condenser is connected to the condensate heating system through a pipeline, and the condensate output from the condenser will reach the condensate heating system through the pipeline, and will be driven by the condensate pump of the condensate heating system, heated by the shaft seal heater, heated by multiple low-pressure heaters, deoxygenated by the deaerator, driven and pressurized by the feed water pump, and heated by multiple high-pressure heaters in sequence, and finally output high-temperature liquid water. Since the pressure of the high-pressure heater is relatively large, the boiling point of water is increased, and the temperature of the output high-temperature liquid water can exceed 100°C. The outlet of the condensate heating system is connected to the evaporators of the six nuclear steam supply system modules through pipelines, and a feed water regulating valve is provided on the pipeline between the outlet of the condensate heating system and each evaporator, and the condensate output by the condensate heating system will be diverted to the six steam generators.

[0077] The nuclear steam supply system module includes a nuclear reactor and an evaporator. There is a circulation pipeline between the nuclear reactor and the evaporator, that is, a circulation pipeline composed of an upward pipeline from the nuclear reactor to the evaporator and a downward pipeline from the evaporator to the nuclear reactor. Each nuclear reactor generates high temperature through nuclear fission to heat helium, and the heated helium is output to the evaporator through the upward pipeline in the form of helium flow. For the evaporator of each nuclear steam supply system module, the high-temperature helium entering the evaporator will exchange heat with the condensed water entering the evaporator, so that the condensed water is vaporized into water vapor, and the high-temperature helium is cooled. The cooled helium will return to the nuclear reactor through the downward pipeline in the form of helium flow.

[0078] The water vapor output from the evaporators of the six nuclear steam supply system modules is collected and then diverted to the steam turbine and the heating system. A main steam regulating valve is provided in front of the steam turbine to adjust the amount of steam entering the steam turbine. After the steam enters the steam turbine, it drives the steam turbine to rotate. The steam turbine is connected to the generator, so when the steam turbine rotates, the generator will generate current through the principle of electromagnetic induction, and the current generated by the generator will be input into the power grid; the steam turbine and the condenser are connected by pipelines, and the steam passing through the steam turbine will enter the condenser through the pipeline to be cooled and liquefied into condensed water. After the steam enters the heating system, the heating system can use the steam to provide heat or mechanical energy to the outside; the heating system and the condenser are connected by pipelines, and the steam passing through the heating system will also enter the condenser through the pipeline to be cooled and liquefied into condensed water.

[0079] Next, continue with the attached Figure 1 Taking the multi-module nuclear thermal power system shown as an example, the feed water flow control logic, nuclear power control logic and primary coolant flow control logic of the nuclear steam supply system module of the multi-module nuclear thermal power system are explained.

[0080] Feedwater flow control logic: determine the thermal power control strategy (such as the thermal power adjustment amount, etc.) based on the flow rate G of condensed water before entering the nuclear steam supply system module, the temperature T of condensed water before entering the nuclear steam supply system module, the pressure P of condensed water before entering the nuclear steam supply system module, the temperature T of steam output by the nuclear steam supply system module, and the main steam pressure measurement value P; determine the feedwater flow setting value based on the module thermal power setting value, the thermal power-feedwater flow steady-state characteristic table, and the thermal power control strategy; and then control the feedwater regulating valve opening of the nuclear steam supply system module based on the feedwater flow setting value and the flow rate G of condensed water before entering the nuclear steam supply system module.

[0081] Nuclear power control logic: determine the hot helium temperature setting value according to the module thermal power setting value and the thermal power-hot helium temperature steady-state characteristic table; determine the helium temperature control strategy (such as the helium temperature adjustment amount) according to the hot helium temperature setting value and the temperature T of the helium flow output by the nuclear steam supply system module; determine the nuclear power setting value according to the module thermal power setting value, the thermal power-nuclear power steady-state characteristic table, and the helium temperature control strategy; and then control the nuclear power of the nuclear reactor based on the nuclear power setting value and the nuclear power measurement value of the nuclear reactor.

[0082] The primary loop coolant flow control logic: determine the steam temperature set value according to the module thermal power set value and the thermal power-steam temperature steady-state characteristic table; determine the steam temperature control strategy (such as steam temperature adjustment amount) according to the steam temperature set value and the temperature T of the steam output by the nuclear steam supply system module; determine the helium flow set value according to the module thermal power set value, the thermal power-helium flow steady-state characteristic table, and the steam temperature control strategy; and then control the speed of the main helium fan based on the helium flow set value and the flow rate G of the helium flow output by the nuclear steam supply system module.

[0083] Next, continue with the attached Figure 1 Taking the multi-module nuclear thermal power system shown as an example, the main steam pressure control logic of the multi-module nuclear thermal power system, that is, the specific content of the method, is introduced in detail.

[0084] Please refer to the attached Figure 2 , which exemplarily shows the process of the main steam pressure control method of the multi-module nuclear thermal power system, including steps S201 to S203.

[0085] In step S201, when the opening of the main steam regulating valve of the multi-module nuclear thermal power system is fixed, a main steam pressure measurement value of the multi-module nuclear thermal power system is obtained.

[0086] Among them, the main steam regulating valve of the multi-module nuclear thermal power system has a fixed opening due to fixed turbine air intake or turbine maintenance, etc. In this case, the main steam pressure of the system cannot be controlled by the main steam regulating valve.

[0087] For example, the main steam pressure measurement value may be acquired in real time based on a pressure sensor disposed on the main steam pipeline.

[0088] In step S202, if the deviation between the main steam pressure measurement value and the main steam pressure setting value of the multi-module nuclear thermal power system is greater than a first threshold, the adjustment amount of the feed water pump speed setting value and the adjustment amount of the thermal power setting value of the multi-module nuclear thermal power system are determined according to the deviation.

[0089] The main steam pressure setting value is the value at which the main steam pressure is expected to be maintained. The first threshold is the tolerance value of the main steam pressure fluctuation, which can be 0 or other values; preferably, the first threshold is not 0 to avoid frequent and complex adjustments when the main steam pressure fluctuates slightly.

[0090] The main steam pressure measurement value and the main steam pressure setting value of the multi-module nuclear thermal power system may be subtracted to obtain a deviation therebetween.

[0091] Exemplarily, the adjustment amount of the feedwater pump speed setting value and the adjustment amount of the thermal power setting value of the multi-module nuclear thermal power system may be determined in the following manner:

[0092] According to the deviation and the first proportional integral control algorithm, the adjustment amount of the feedwater pump speed setting value of the multi-module nuclear thermal power system is determined. For example, the adjustment amount of the feedwater pump speed setting value is determined according to the following formula:

[0093]

[0094] In the above formula, G 1 (s) is the adjustment amount of the feed water pump speed setting value, k 1 is the first proportional control gain, T 1 is the first integration time constant.

[0095] According to the deviation and the second proportional integral control algorithm, the adjustment amount of the thermal power setting value of the multi-module nuclear thermal power system is determined. For example, the adjustment amount of the thermal power setting value is determined according to the following formula:

[0096]

[0097] In the above formula, G 2 (s) is the adjustment amount of the thermal power setting value, k 2 is the second proportional control gain, T 2 is the second integration time constant.

[0098] In step S103, the feedwater pump speed setting value of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the feedwater pump speed setting value, and the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setting value to reduce the deviation.

[0099] Exemplarily, the feed water pump speed setting value of the multi-module nuclear thermal power system can be adjusted in the following manner: based on the adjustment amount of the feed water pump speed setting value, the hydraulic coupling scoop position setting value of the feed water pump of the multi-module nuclear thermal power system is adjusted to adjust the speed of the feed water pump.

[0100] As another example, the thermal power set point of the nuclear steam supply system module may be adjusted in at least one of the following ways.

[0101] Mode 1: The thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setting value, so that the nuclear steam supply system module adjusts the feed water flow rate based on the adjusted thermal power setting value. For example, the nuclear steam supply system module can control the feed water flow rate according to the feed water flow rate control logic of the above-mentioned nuclear steam supply system module. This mode can achieve a balance between the feed water flow rate and the steam flow rate of the heating system.

[0102] Mode 2: The thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setting value, so that the nuclear steam supply system module adjusts the nuclear power based on the adjusted thermal power setting value. For example, the nuclear steam supply system module can control the nuclear power according to the nuclear power control logic of the nuclear steam supply system module, such as adjusting the rod position of the control rod to adjust the nuclear power.

[0103] Mode 3: The thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setting value, so that the nuclear steam supply system module adjusts the primary coolant flow rate based on the adjusted thermal power setting value. For example, the nuclear steam supply system module can control the primary coolant flow rate according to the primary coolant flow rate control logic of the nuclear steam supply system module. This mode can achieve a balance between thermal power and nuclear power.

[0104] The above-mentioned method for adjusting the thermal power set value of the nuclear steam supply system module can be applied to part or all of the nuclear steam supply system modules of the multi-module nuclear thermal power system; preferably, when this step adjusts the thermal power set value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power set value, the thermal power set value of at least one nuclear steam supply system module participating in the main steam pressure control in the multi-module nuclear thermal power system can be adjusted based on the adjustment amount of the thermal power set value.

[0105] For example, at least one nuclear steam supply system module participating in the main steam pressure control can be determined from among all the nuclear steam supply system modules of the multi-module nuclear thermal power system according to the deviation; Figure 1 Taking the multi-module nuclear thermal power system shown as an example, if the deviation reaches the first threshold but does not reach x times of the first threshold, the n nuclear steam supply system modules in the multi-module nuclear thermal power system are determined as nuclear steam supply system modules participating in the main steam pressure control; if the deviation reaches x times of the first threshold but does not reach y times of the first threshold, the m nuclear steam supply system modules in the multi-module nuclear thermal power system are determined as nuclear steam supply system modules participating in the main steam pressure control; if the deviation reaches y times of the first threshold, the p nuclear steam supply system modules in the multi-module nuclear thermal power system are determined as nuclear steam supply system modules participating in the main steam pressure control, wherein x is less than y, and m is greater than n and less than p.

[0106] For another example, at least one nuclear steam supply system module participating in the main steam pressure control can be determined in all the nuclear steam supply system modules of the multi-module nuclear thermal power system according to the user's instruction. That is, the user (e.g., the staff of the multi-module nuclear thermal power system) has pre-configured the nuclear steam supply system module participating in the main steam pressure control.

[0107] In the above two examples, it is preferred that the number of nuclear steam supply system modules participating in the main steam pressure control does not exceed half of all the nuclear steam supply system modules of the multi-module nuclear thermal power system.

[0108] This step adjusts the feedwater pump speed setting value and the thermal power setting value of the nuclear steam supply system module in order to reduce the deviation between the main steam measurement value and the main steam setting value, and a cutoff condition can be preset to end the adjustment of this step. Preferably, this step can be performed in the following manner: based on the adjustment amount of the feedwater pump speed setting value, the feedwater pump speed setting value of the multi-module nuclear thermal power system is adjusted, and based on the adjustment amount of the thermal power setting value, the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted until the deviation is reduced to below a second threshold value, wherein the second threshold value is less than the first threshold value.

[0109] By setting the second threshold to be smaller than the first threshold, it is possible to avoid too frequent adjustment of the feedwater pump speed and the thermal power of the nuclear steam supply system module when the main steam measurement value fluctuates, thereby avoiding fluctuations in various process parameters of the system caused by frequent adjustments.

[0110] In summary, when the set value of the main steam pressure deviates from the measured value, the method reduces the above deviation by adjusting the system's feedwater pump speed and the thermal power of at least one nuclear steam supply system module. When the opening of the main steam regulating valve is fixed, the method can quickly respond to the thermal load fluctuation of the heating system, so that the steam pressure entering the heating system meets the thermal load demand of the heating system, thereby improving the stability of the heating effect of the heating system.

[0111] Please refer to the attached Figure 3 , which exemplarily shows the control logic of the primary frequency modulation method obtained by combining the above embodiments:

[0112] First, the user (eg, a staff member of a multi-module nuclear thermal power system) sets the number and serial number of nuclear steam supply system modules participating in main steam pressure control in the system, that is, selects certain nuclear steam supply system modules to participate in main steam pressure control.

[0113] Next, the main steam pressure measurement value is obtained and compared with the main steam pressure set value, and the deviation between the two is sent to the main steam pressure controller. When the deviation between the two is greater than a first threshold value, the main steam pressure controller adjusts the feed water pump speed set value and the thermal power set value of the nuclear steam supply system module involved in the main steam pressure control according to the deviation.

[0114] Attach Figure 1Taking the multi-module nuclear thermal power system shown as an example, the typical application scenario of the method is described in detail. The staff selected three nuclear steam supply system modules to participate in the main steam pressure control. At this time, when the load of the heating system decreases, the main steam pressure rises, the feedwater flow of all nuclear steam supply system modules decreases, and the steam temperature at the evaporator outlet rises, which in turn causes the main steam temperature to rise. These deviations drive the control method of the present invention to take action. The main steam pressure controller reduces the hydraulic coupling spoon position setting value through the proportional integral algorithm, and directly and quickly compensates the main steam pressure by reducing the feedwater pump speed. The main steam pressure controller reduces the selected nuclear steam supply system module thermal power setting value through the proportional integral algorithm, and achieves the steam flow balance corresponding to the total feedwater flow and the load of the heating system by reducing the feedwater flow of these modules. The steam temperature controllers of all nuclear steam supply system modules reduce the helium flow setting value of the first circuit, and maintain the evaporator outlet steam temperature by reducing the helium flow of the first circuit. If the module thermal power setting value remains unchanged, the helium flow of the first circuit returns to the original value after a transient state, otherwise it follows the set power decrease. The nuclear power controller of the selected nuclear steam supply system module reduces the nuclear power set point and balances the nuclear power with the thermal power by reducing the control rod position.

[0115] The reason why the method simultaneously adjusts the feedwater pump speed and the thermal power set value of the selected part of the nuclear steam supply system modules is that: when the main steam pressure measurement value deviates from the main steam pressure set value, if the main steam pressure deviation is reduced by only adjusting the rapid response of the feedwater pump speed, the feedwater flow rate will change, and the change of the feedwater flow rate will further drive the feedwater flow controller to maintain the feedwater flow rate at the set value level, which in turn will increase the deviation between the main steam pressure and the set value, and have the opposite effect. Therefore, the present invention needs to synchronously adjust the thermal power set value of the nuclear steam supply system module participating in the main steam pressure control while adjusting the feedwater pump speed, so as to maintain the feedwater flow rate consistent with the steam flow rate corresponding to the heating system.

[0116] According to a second aspect of the embodiment of the present disclosure, a main steam pressure control device for a multi-module nuclear thermal power system is provided. Figure 4 , the device comprises:

[0117] The acquisition module 401 is used to acquire the main steam pressure measurement value of the multi-module nuclear thermal power system when the opening of the main steam regulating valve of the multi-module nuclear thermal power system is fixed;

[0118] A determination module 402 is used to determine an adjustment amount of a feedwater pump speed setting value and an adjustment amount of a thermal power setting value of the multi-module nuclear thermal power system according to the deviation between the main steam pressure measurement value and the main steam pressure setting value of the multi-module nuclear thermal power system if the deviation between the main steam pressure measurement value and the main steam pressure setting value of the multi-module nuclear thermal power system is greater than a first threshold value;

[0119] The adjustment module 403 is used to adjust the feedwater pump speed of the multi-module nuclear thermal power system based on the adjustment amount of the feedwater pump speed setting value, and to adjust the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setting value, so as to reduce the deviation.

[0120] In one embodiment of the present disclosure, the determining module is used to:

[0121] Determining an adjustment amount of a feedwater pump speed setting value of the multi-module nuclear thermal power system according to the deviation and a first proportional-integral control algorithm;

[0122] An adjustment amount of a thermal power set point of the multi-module nuclear thermal power system is determined based on the deviation and a second proportional-integral control algorithm.

[0123] In one embodiment of the present disclosure, when the adjustment module is used to adjust the feedwater pump speed setting value of the multi-module nuclear thermal power system based on the adjustment amount of the feedwater pump speed setting value, it is used to:

[0124] Based on the adjustment amount of the feed water pump speed setting value, the hydraulic coupling scoop position setting value of the feed water pump of the multi-module nuclear thermal power system is adjusted to adjust the speed of the feed water pump.

[0125] In one embodiment of the present disclosure, when the adjustment module is used to adjust the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setting value, it is used to:

[0126] The thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setting value, so that the nuclear steam supply system module adjusts the feed water flow based on the adjusted thermal power setting value.

[0127] In one embodiment of the present disclosure, when the adjustment module is used to adjust the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setting value, it is used to:

[0128] The thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setting value, so that the nuclear steam supply system module adjusts the nuclear power based on the adjusted thermal power setting value.

[0129] In one embodiment of the present disclosure, when the adjustment module is used to adjust the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setting value, it is used to:

[0130] The thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setting value, so that the nuclear steam supply system module adjusts the primary loop coolant flow based on the adjusted thermal power setting value.

[0131] In one embodiment of the present disclosure, the device further includes a selection module, configured to:

[0132] According to the deviation, determining at least one nuclear steam supply system module participating in main steam pressure control among all the nuclear steam supply system modules of the multi-module nuclear thermal power system;

[0133] When the adjustment module is used to adjust the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setting value, it is used to:

[0134] Based on the adjustment amount of the thermal power setting value, the thermal power setting value of at least one nuclear steam supply system module participating in the main steam pressure control in the multi-module nuclear thermal power system is adjusted.

[0135] In one embodiment of the present disclosure, the device further includes a selection module, configured to:

[0136] Determining at least one nuclear steam supply system module participating in main steam pressure control among all the nuclear steam supply system modules of the multi-module nuclear thermal power system according to a user instruction;

[0137] When the adjustment module is used to adjust the thermal power set value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power set value, it is used to: adjust the thermal power set value of at least one nuclear steam supply system module participating in the main steam pressure control in the multi-module nuclear thermal power system based on the adjustment amount of the thermal power set value.

[0138] In one embodiment of the present disclosure, the adjustment module is used to:

[0139] The feedwater pump speed setting value of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the feedwater pump speed setting value, and the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setting value, until the deviation is reduced below a second threshold, wherein the second threshold is smaller than the first threshold.

[0140] In one embodiment of the present disclosure, the main steam regulating valve of the multi-module nuclear thermal power system is used to fix the opening when the turbine air intake is fixed or the turbine is under maintenance.

[0141] Regarding the device in the above embodiment, the specific manner in which each module performs the operation has been described in detail in the embodiment of the first aspect related to the method, and will not be elaborated here.

[0142] According to a third aspect of an embodiment of the present disclosure, there is provided a computer program product, comprising a computer program / instruction, which implements the steps of the method described in the first aspect when the computer program / instruction is executed by a processor.

[0143] According to the fourth aspect of the embodiment of the present disclosure, please refer to the attached Figure 5 , which exemplarily shows a block diagram of an electronic device. For example, the device 500 may be a mobile phone, a computer, a digital broadcast terminal, a messaging device, a game console, a tablet device, a medical device, a fitness device, a personal digital assistant, etc.

[0144] Reference Figure 5 , device 500 may include one or more of the following components: a processing component 502 , a memory 504 , a power component 506 , a multimedia component 508 , an audio component 510 , an input / output (I / O) interface 512 , a sensor component 514 , and a communication component 516 .

[0145] The processing component 502 generally controls the overall operation of the device 500, such as operations associated with display, phone calls, data communications, camera operations, and recording operations. The processing component 502 may include one or more processors 520 to execute instructions to complete all or part of the steps of the above-mentioned method. In addition, the processing component 502 may include one or more modules to facilitate the interaction between the processing component 502 and other components. For example, the processing component 502 may include a multimedia module to facilitate the interaction between the multimedia component 508 and the processing component 502.

[0146] The memory 504 is configured to store various types of data to support operations on the device 500. Examples of such data include instructions for any application or method operating on the device 500, contact data, phone book data, messages, pictures, videos, etc. The memory 504 can be implemented by any type of volatile or non-volatile storage device or a combination thereof, such as static random access memory (SRAM), electrically erasable programmable read-only memory (EEPROM), erasable programmable read-only memory (EPROM), programmable read-only memory (PROM), read-only memory (ROM), magnetic memory, flash memory, magnetic disk or optical disk.

[0147] Power component 506 provides power to various components of device 500. Power component 506 may include a power management system, one or more power supplies, and other components associated with generating, managing, and distributing power for device 500.

[0148] The multimedia component 508 includes a screen that provides an output interface between the device 500 and the user. In some embodiments, the screen may include a liquid crystal display (LCD) and a touch panel (TP). If the screen includes a touch panel, the screen may be implemented as a touch screen to receive input signals from the user. The touch panel includes one or more touch sensors to sense touch, slide, and gestures on the touch panel. The touch sensor may not only sense the boundaries of the touch or slide action, but also detect the duration and pressure associated with the touch or slide operation. In some embodiments, the multimedia component 508 includes a front camera and / or a rear camera. When the device 500 is in an operating mode, such as a shooting mode or a video mode, the front camera and / or the rear camera may receive external multimedia data. Each front camera and the rear camera may be a fixed optical lens system or have a focal length and optical zoom capability.

[0149] The audio component 510 is configured to output and / or input audio signals. For example, the audio component 510 includes a microphone (MIC), and when the device 500 is in an operating mode, such as a call mode, a recording mode, and a speech recognition mode, the microphone is configured to receive an external audio signal. The received audio signal can be further stored in the memory 504 or sent via the communication component 516. In some embodiments, the audio component 510 also includes a speaker for outputting audio signals.

[0150] I / O interface 512 provides an interface between processing component 502 and peripheral interface modules, such as keyboards, click wheels, buttons, etc. These buttons may include but are not limited to: a home button, a volume button, a start button, and a lock button.

[0151] The sensor assembly 514 includes one or more sensors for providing various aspects of status assessment for the device 500. For example, the sensor assembly 514 can detect the open / closed state of the device 500, the relative positioning of components, such as the display and keypad of the device 500, and the sensor assembly 514 can also detect the position change of the device 500 or a component of the device 500, the presence or absence of user contact with the device 500, the orientation or acceleration / deceleration of the device 500, and the temperature change of the device 500. The sensor assembly 514 can also include a proximity sensor configured to detect the presence of nearby objects without any physical contact. The sensor assembly 514 can also include a light sensor, such as a CMOS or CCD image sensor, for use in imaging applications. In some embodiments, the sensor assembly 514 can also include an acceleration sensor, a gyroscope sensor, a magnetic sensor, a pressure sensor, or a temperature sensor.

[0152] The communication component 516 is configured to facilitate wired or wireless communication between the device 500 and other devices. The device 500 can access a wireless network based on a communication standard, such as WiFi, 2G or 3G, 4G or 5G or a combination thereof. In an exemplary embodiment, the communication component 516 receives a broadcast signal or broadcast-related information from an external broadcast management system via a broadcast channel. In an exemplary embodiment, the communication component 516 also includes a near field communication (NFC) module to facilitate short-range communication. For example, the NFC module can be implemented based on radio frequency identification (RFID) technology, infrared data association (IrDA) technology, ultra-wideband (UWB) technology, Bluetooth (BT) technology and other technologies.

[0153] In an exemplary embodiment, the device 500 can be implemented by one or more application-specific integrated circuits (ASICs), digital signal processors (DSPs), digital signal processing devices (DSPDs), programmable logic devices (PLDs), field programmable gate arrays (FPGAs), controllers, microcontrollers, microprocessors, or other electronic components to perform the main steam control method of the above-mentioned electronic equipment.

[0154] In a fifth aspect, the present disclosure, in an exemplary embodiment, further provides a non-transitory computer-readable storage medium including instructions, such as a memory 504 including instructions, and the instructions can be executed by a processor 520 of a device 500 to complete the main steam control method of the electronic device. For example, the non-transitory computer-readable storage medium can be a ROM, a random access memory (RAM), a CD-ROM, a magnetic tape, a floppy disk, an optical data storage device, and the like.

[0155] Those skilled in the art will readily appreciate other embodiments of the present disclosure after considering the specification and practicing the disclosure disclosed herein. The present disclosure is intended to cover any variations, uses, or adaptations of the present disclosure that follow the general principles of the present disclosure and include common knowledge or customary techniques in the art that are not disclosed in the present disclosure. The description and examples are to be considered exemplary only, and the true scope and spirit of the present disclosure are indicated by the following claims.

[0156] It should be understood that the present disclosure is not limited to the exact structures that have been described above and shown in the drawings, and that various modifications and changes may be made without departing from the scope thereof. The scope of the present disclosure is limited only by the appended claims.

Claims

1. A main steam pressure control method for a multi-module nuclear thermal power system, characterized in that: The method comprises: When the opening of the main steam regulating valve of the multi-module nuclear thermal power system is fixed, obtaining a main steam pressure measurement value of the multi-module nuclear thermal power system; If the deviation between the main steam pressure measurement value and the main steam pressure setting value of the multi-module nuclear thermal power system is greater than a first threshold value, determining an adjustment amount of a feedwater pump speed setting value and an adjustment amount of a thermal power setting value of the multi-module nuclear thermal power system according to the deviation; The feedwater pump speed setting value of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the feedwater pump speed setting value, and the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setting value to reduce the deviation.

2. The main steam pressure control method of a multi-module nuclear thermal power system according to claim 1, characterized in that: The step of determining the adjustment amount of the feedwater pump speed setting value and the thermal power setting value of the multi-module nuclear thermal power system according to the deviation includes: Determining an adjustment amount of a feedwater pump speed setting value of the multi-module nuclear thermal power system according to the deviation and a first proportional-integral control algorithm; An adjustment amount of a thermal power set point of the multi-module nuclear thermal power system is determined based on the deviation and a second proportional-integral control algorithm.

3. The main steam pressure control method of a multi-module nuclear thermal power system according to claim 1, characterized in that: The adjusting the feedwater pump speed setting value of the multi-module nuclear thermal power system based on the adjustment amount of the feedwater pump speed setting value includes: Based on the adjustment amount of the feed water pump speed setting value, the hydraulic coupling scoop position setting value of the feed water pump of the multi-module nuclear thermal power system is adjusted to adjust the speed of the feed water pump.

4. The main steam pressure control method of a multi-module nuclear thermal power system according to claim 1, characterized in that: The step of adjusting the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setting value comprises: The thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setting value, so that the nuclear steam supply system module adjusts the feed water flow based on the adjusted thermal power setting value.

5. The main steam pressure control method of a multi-module nuclear thermal power system according to claim 1, characterized in that: The step of adjusting the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setting value comprises: The thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setting value, so that the nuclear steam supply system module adjusts the nuclear power based on the adjusted thermal power setting value.

6. The main steam pressure control method of a multi-module nuclear thermal power system according to claim 1, characterized in that: The step of adjusting the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setting value comprises: The thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setting value, so that the nuclear steam supply system module adjusts the primary loop coolant flow based on the adjusted thermal power setting value.

7. The main steam pressure control method of a multi-module nuclear thermal power system according to claim 1, characterized in that: The method further comprises: According to the deviation, determining at least one nuclear steam supply system module participating in main steam pressure control among all nuclear steam supply system modules of the multi-module nuclear thermal power system; The step of adjusting the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setting value comprises: Based on the adjustment amount of the thermal power setting value, the thermal power setting value of at least one nuclear steam supply system module participating in the main steam pressure control in the multi-module nuclear thermal power system is adjusted.

8. The main steam pressure control method of a multi-module nuclear thermal power system according to claim 1, characterized in that: The method further comprises: Determining at least one nuclear steam supply system module participating in main steam pressure control among all the nuclear steam supply system modules of the multi-module nuclear thermal power system according to a user instruction; The step of adjusting the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setting value comprises: Based on the adjustment amount of the thermal power setting value, the thermal power setting value of at least one nuclear steam supply system module participating in the main steam pressure control in the multi-module nuclear thermal power system is adjusted.

9. The main steam pressure control method of a multi-module nuclear thermal power system according to claim 1, characterized in that: The adjusting amount of the feedwater pump speed setting value is used to adjust the feedwater pump speed setting value of the multi-module nuclear thermal power system, and the adjusting amount of the thermal power setting value is used to adjust the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system to reduce the deviation, including: The feedwater pump speed setting value of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the feedwater pump speed setting value, and the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system is adjusted based on the adjustment amount of the thermal power setting value, until the deviation is reduced below a second threshold, wherein the second threshold is smaller than the first threshold.

10. The main steam pressure control method of a multi-module nuclear thermal power system according to claim 1, characterized in that: The main steam regulating valve of the multi-module nuclear thermal power system is used to fix the opening when the air intake of the steam turbine is fixed or the steam turbine is under maintenance.

11. A main steam pressure control device for a multi-module nuclear thermal power system, characterized in that: The device comprises: An acquisition module, used for acquiring a main steam pressure measurement value of the multi-module nuclear thermal power system when the opening of the main steam regulating valve of the multi-module nuclear thermal power system is fixed; a determination module, configured to determine an adjustment amount of a feedwater pump speed setting value and an adjustment amount of a thermal power setting value of the multi-module nuclear thermal power system according to the deviation between the main steam pressure measurement value and the main steam pressure setting value of the multi-module nuclear thermal power system if the deviation between the main steam pressure measurement value and the main steam pressure setting value of the multi-module nuclear thermal power system is greater than a first threshold value; An adjustment module is used to adjust the feedwater pump speed of the multi-module nuclear thermal power system based on the adjustment amount of the feedwater pump speed setting value, and to adjust the thermal power setting value of at least one nuclear steam supply system module of the multi-module nuclear thermal power system based on the adjustment amount of the thermal power setting value, so as to reduce the deviation.

12. A computer program product comprising a computer program / instructions, characterized in that When the computer program / instructions are executed by a processor, the steps of the method according to any one of claims 1 to 10 are implemented.

13. An electronic device, characterized in that: The electronic device comprises a memory and a processor, wherein the memory is used to store computer instructions executable on the processor, and the processor is used to implement the method according to any one of claims 1 to 10 when executing the computer instructions.

14. A computer-readable storage medium having a computer program stored thereon, characterized in that: When the program is executed by a processor, the method according to any one of claims 1 to 10 is implemented.

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